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dc.contributor.authorNava Dominguez, A.
dc.contributor.authorHuang, Xianmin
dc.contributor.authorGaudet, Michel
dc.contributor.authorKhumsa-Ang, Kittima
dc.contributor.authorMendoza España, Alberto D'Ansi
dc.contributor.authorChow, Jimmy
dc.contributor.authorRoubtsov, Danila
dc.contributor.authorNamburi, Hygreeva
dc.date.accessioned2025-08-20T09:22:25Z
dc.date.available2025-08-20T09:22:25Z
dc.date.copyright5/8/2025 12:00:00 AM
dc.date.issued2025
dc.identifier.issn2332-8983
dc.identifier.otherners_011_03_031301.pdf
dc.identifier.urihttp://yetl.yabesh.ir/yetl1/handle/yetl/4308170
dc.description.abstractThe supercritical water-cooled reactor (SCWR) is one of the six concepts selected by the generation-IV international forum (GIF) for future research. This technology is a natural evolutionary step of the current water-cooled reactors. Canada is a participant of the GIF, and under this international endeavor developed the Canadian SCWR, which is a 1200 MWe concept. However, due to high capital cost associated with building large units, the nuclear industry rekindled an old concept: Small reactors (SRs), and now small modular reactors (SMRs). These reactors are poised to reduce the financial risks associated with large units, and also potentially offer more flexibility as modules can be prefabricated and transported to the construction site for assembly. As a result, numerous domestic and international programs were established to support the development and deployment of SMRs. The ECC-SMART project was proposed to develop a supercritical water-cooled SMR. Canada joined this collaboration, and under this project alongside the GIF SCWR and IAEA CRP platforms, a new Canadian supercritical water-cooled small modular reactor (SCW-SMR) was proposed and developed. This concept is based on the experience and lessons learned during the development of the Canadian SCWR. An overview of a multidisciplinary approach that led to the concept is presented in this paper, consisting of a market study, thermodynamics and energy conversion, reactor physics, thermal hydraulics, materials and chemistry, and safety assessments.
dc.publisherThe American Society of Mechanical Engineers (ASME)
dc.titleProgress on a Preconceptual Supercritical Water-Cooled Small Modular Reactor
dc.typeJournal Paper
dc.journal.volume11
dc.journal.issue3
dc.journal.titleJournal of Nuclear Engineering and Radiation Science
dc.identifier.doi10.1115/1.4068326
dc.journal.fristpage31301-1
dc.journal.lastpage31301-20
dc.page20
dc.treeJournal of Nuclear Engineering and Radiation Science:;2025:;volume( 011 ):;issue: 003
dc.contenttypeFulltext


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